ML19329A812
| ML19329A812 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse |
| Issue date: | 10/04/1977 |
| From: | Zell J TOLEDO EDISON CO. |
| To: | |
| Shared Package | |
| ML19329A805 | List: |
| References | |
| NUDOCS 8001150707 | |
| Download: ML19329A812 (2) | |
Text
s e
~ ~ ~ ~ *
- ' ~
y y o__
LICENSEE EVENT REPORT pl l 1 Ij coNinot stocs c
mm
.m ~,........
<,w
,v.~c E.l o lH I DIB l S l1]
l0 01 --l Ol 01 NI PIF i -10 l 3l l 4l1l1 l1l1J,lA03l
...,s
,, m C.,.co. m e' v e. m o........
...o......
lg 0 t 5 i O. ; Oi 34 1 6 019 t o ll 17171 111010141717J i
1 con i EvtNTOf5calPfacN
@ gat 1510 hours0.0175 days <br />0.419 hours <br />0.0025 weeks <br />5.74555e-4 months <br /> on September 1, 1977, Reactor Coolant Pump 1-2-1 tripped 7 83 gldue to low seal injection and component cooling water flow.
In Action g l Statement of Technical Specification 3.4.1.
Reactor Coolant Pump 1-2-1 E DL,e-started at 1524 hours0.0176 days <br />0.423 hours <br />0.00252 weeks <br />5.79882e-4 months <br /> on September 1, 1977.
(NP-33-77-76) l r
7 83 8L
't....
..m.
a:=.
m,..
ii:D $
IP[k5tPf$((Xl
'"Y'"
[1';"9]'4"Y} "' [' ~
~
0 F
53 30 st 42 37 4
44 43 43 CAuSF oESCRIPfloM lThe cause of this occurrence is personnel error. An operator mistakenly g
l closed valve IA 601 which supplies instrument air to the normal makeup
-j 8
eo g l flow Control valve.
a, g a'I'E
( BJ t EDI y1 vest a st Arus ces (5 av {
j DeStowCav ot;5Cnerf eoas NA l
j i i 7 G S
10 32 44 45 e6 50 at D os s'
C a.otret or ac.svetv toCAiso.e ce m.LC ASC 8
LZ_J. IZJ l NA 1
l NA l
7 8 9
0 44 as 90 Ptn50NNEL EXPOS.URES g.g oeg... o=
- -e a i, s i.
i i2 m
PER$o8eNtt INJusetts i
[
l l l A l
\\
of F581E Co*8SEout8ectS l NA l
i t9 N
LOSS om oAMAGE To F ACIUTY tvet ossemeevion 3Z t NA I
l i a b
w rue ucirv i
@ l NA l
- es Ao T eo**AL F ACf oMr.
h*I I
,s
\\-)
wl.
3 1
l 4197 '259-5000, Ext. 267
(
Jim Zell l
80011507C7
.=
y'
'~
~
TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT 0 SUPPLEMENTAL INFORMATION FOR LER NP-31-77-76 b
,3 DATE OF EVENT: September 1, 1977 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE: Reactor Coolant Pump (RCP) 1-2-1 tripped causing single pump operation in a Reactor Coolant Loop.
Conditions Prior to Occurrence: The plant was in Mode 1, with Power (MWT) = 10%,
and Load (MWE) = 0.
Description of Occurrence: At 1510 hours0.0175 days <br />0.419 hours <br />0.0025 weeks <br />5.74555e-4 months <br /> on September 1, 1977, the component cool-ing water flow to RCP l-2-1 was oscillating at its low flow setpoint. At the same 1
ti=e, seal injection flow to RCP l-2-1 dropped below its low flow setpoint due to Normal Makeup Flow Control Valve MU 32 failing full open. The control interlock which requires either seal injection or component cooling water flow was not satis-fled and, therefore, tripped RCP l-2-1.,,
This placed the station in the Action Statement of Technical Specification 3.4.1 which requires all four reactor coolant pumps operatir.:;; while in Mode 1.
1 Designation of Apcarent Cause of Occurrence: This occurrence was due to personnel error. An operator mistakenly shut Instrument Air Valve IA 601.(instead,of SA 601) which supplies the pneumatic operator of Normal Makeup Flow Control valve MU 32, causing it to fail open with a resultant drop.in flow to RCP l-2-l' seal injection.
The wrong valve was shut due to the close proximity of valve IA 601 to SA 601.
Analysis of Occurrence: There was no danger to the health and safety of the public or to station personnel. The three operating reactor coolant pumps provided nore than sufficient flow to remove the heat in the reactor core.
Corrective Action: Instrument Air Valve IA 601 which supplies control air for Normal Makeup Flow Control Valve MU 32 was found to be closed and was immediately re-opened. Seal injection flow was re-established and RCP l-2-1 restarted at 1524 hours0.0176 days <br />0.423 hours <br />0.00252 weeks <br />5.79882e-4 months <br /> on September 1, 1977. Since the error was due to the unusual situation of two similarly labeled valves being in close proximity, IA 601 was relabeled as IA 603 and the appropriate procedure modifications have been made.
Failure Data: There has been one previous failure of a Reactor Co'olant Pump,
.NP-33-77-64, but the cause was a capacitor failure.
~
-